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| number = ML23171A913
| number = ML23171A913
| issue date = 06/20/2023
| issue date = 06/20/2023
| title = Amse, Section XI, Fifth 10 Year Inspection Interval, Inservice Inspection, System Pressure Test, Containment Inspection, and Repair and Replacement Programs, Owners Activity Report
| title = Amse, Section XI, Fifth 10 Year Inspection Interval, Inservice Inspection, System Pressure Test, Containment Inspection, and Repair and Replacement Programs, Owner’S Activity Report
| author name = Sivaraman M
| author name = Sivaraman M
| author affiliation = Tennessee Valley Authority
| author affiliation = Tennessee Valley Authority
Line 15: Line 15:


=Text=
=Text=
{{#Wiki_filter:}}
{{#Wiki_filter:VALLEY TENNESSEE 1\\14 AUTHORITY
 
Post Office Box 2000, Decatur, Alabama 35609-2000
 
June 20, 2023 10 CFR 50.55a
 
ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, D.C. 20555-0001
 
Browns Ferry Nuclear Plant, Unit 2 Renewed Facility Operating License No. DPR-52 NRC Docket No. 50-260
 
==Subject:==
American Society of Mechanical Engineers, Section XI, Fifth 10 Year Inspection Interval, Inservice Inspection, System Pressure Test, Containment Inspection, and Repair and Replacement Programs, Owners Activity Report for Browns Ferry Nuclear Plant, Unit 2, Cycle 22 Operation
 
The Tennessee Valley Authority is submitting the Br owns Ferry Nuclear Plant (BFN), American Society of Mechanical Engineers (ASME), Section XI, Owners Activity Report for BFN, Unit 2, Cycle 22 Operation. The report is contained in the enclosure to this letter and is in accordance with the requirements of ASME Code Case N-532-5, Repair/Replacement Documentation Requirements and Inservice Summary Report Preparation and Submission, Section XI, Division 1.
 
The report is an overview of the inservice examination results that were performed on components within the ASME Section XI boundary, up to and including the BFN, Unit 2, Cycle 22 refueling outage, during the third inspection period of the Fifth 10 Year Inspection Interval. The applicable provisions of the ASME Code Case N-532-5 require t hat this report be submitted within 90 calendar days of the completion of each refueling outage. The BFN, Unit 2, Cycle 22 refueling outage ended on March 22, 2023. Accordingly, this submittal is due by June 20, 2023.
U.S. Nuclear Regulatory Commission Page 2 June 20, 2023
 
There are no new regulatory commitments contained in this letter. Should you have any questions concerning this submittal, please contact C. L. Vaughn, Site Licensing Manager, at (256) 729-2636.
 
Respectfully,
 
Manu Sivaraman Site Vice President
 
==Enclosure:==
American Society of Mechanical Engineers, Section XI, Fifth 10 Year Inspection Interval, Inservice Inspection, System Pressure Test, Containment Inspection, and Repair and Replacement Programs, Owners Activity Report for Browns Ferry Nuclear Plant, Unit 2, Cycle 22 Operation
 
cc (Enclosure): NRC Regional Administrator - Region II NRC Senior Resident Inspector - Browns Ferry Nuclear Plant NRC Project Manager - Browns Ferry Nuclear Plant
 
Enclosure
 
Tennessee Valley Authority
 
Browns Ferry Nuclear Plant Unit 2
 
American Society of Mechanical Engineers, Section XI, Fifth 10 Year Inspection Interval, Inservice Inspection, System Pressure Test, Containment Inspection, and Repair and Replacement Programs, Owners Activity Report for Browns Ferry Nuclear Plant, Unit 2, Cycle 22 Operation
 
See Enclosed
 
FORM OAR~1 OWNER'S ACTIVITY REPORT
 
Report Numbe r --"8'-'-F...,_N,..,U"-'2'-'-R_,_,2.,2~---- - ------- ----- ----- ------- ------- -
 
Plant Browns Ferry Nuc lear Pl<1nl. P 0. Box 2000 Decatur AL 35609
 
Unit No. - ---,-~2~-,- al service date March 1 1975 Refueling Outage no. --"'R~e~fl~'e"'li'-'n"'g_,O"-'u'-'-l'"ag"'e"-"-2,._2 __
(ir apph.: abl iC!-) Commerc i
 
Current Inspect ion Interval Fifth Ten Year inspection Interval
{ 151. 2M, 31 C1. m tier)
 
Current Inspection Period T~h~i~rd~P~e~ri=od~------- - -------::-c--::: -,-,-,---- ------ -------- p s,. 2n d, :!;, d)
 
2007 Edition, 2008 Addenda (ISi)
Edition and Addenda of Section XI applicable lo l11e inspection plans =2=0~13~E~d~it,~*o~n~(C=IS~IL) ---- ------ -------~
 
O-TPP-ENG-376, Revision 0004, 11/18/2022 O-Tl-364, Rev ision 0025, 02/06/2023 Dale and Rev ision of inspection plan 0-TPP-E NG-467 Revision 0001 01/12/2023
 
Edition and Addenda of Section XI applicable lo repairs and replacements, if different than the inspection plan ~N=IA~-
 
Code Cases used for inspection and evaluation : N-532-5 N-613-2 N-716-1 N-751 N-854. and N-864 (1I ap p hc.able, 1nc lu d 1r\\Q Crl:!>C~ mQd1f;ed b)' C a se N -S-32 anel la!Cr fC','1$kil'I~)
 
CERTIFICATE OF CONFORMANCE
 
I certify that (a) lhe statements made in this report are correc t (b) the ex aminations and tests meet the Inspection Plan as required by the ASME Code, Section XI ; and (c) the repair/replacement act ivities and evaluations supporting the completion of U2R22 conform to the requ iremen ts of Section XL '"' '"'""!l oota~ c ou mne r) s,,,.,f?~
 
CERTIFICATE OF INSERVICE INSPECTION
 
I, the und ersigned. holding a va lid commiss ion issued by the National Board of Boiler and Pressure Vessel Inspectors and employed by The Hartford Steam Bo iler lnspeclion and Insurance Company of Hartford Connect icut have inspected the items described in this Owne rs Activity Report and state that, to the best of my knowledge a nd belief, lhe Owner has performed all activities represented by this report in accordance with the requirements of Section XI.
By signing this certificate neither the Ins pec tor nor his emp loyer makes any warranty, expressed or implied, concerning the repair/ rep lacemen t act ivities and evalua tion described in this report. Furthermore, ne ither the Inspector nor his employer shall be liable in any manner for any personal 1n1ury o(. roperty damage or a loss of any kind arising from or connected with this Inspection P/~7, Comm issions f'Sf3. I ~q 71 L, N R...
FORM OAR-1 OWNER'S ACTIVITY REPORT
 
TABLES Report Number BFNU2R22 -------------------------------
PI ant Browns Ferry Unit No. 2 Commercia l service date 03/01/1975 Refueling outage no. 22 - ---
Cur rent inspection interval 5th Current inspection peri----- ----- - -od 3rd TABLE 1 ITEMS WITH FLAWS OR RELEVANT CONDITIONS THAT REQUIRE EVALUATIONS FOR CONTINUED SERVICE Exam ination Category and Item Number Item Description Evaluation Description F-A / F1.30C Residual Heat Removal Service Water NOi U2R22 -001 Variable Suppo rt, 2-4 7B450H0041 A variable spring support setting was found out of tolerance/ out of its load seeing range. It was determined that the as-found setting was w ithin the allowable working range, and that the va riable spring support wou ld have bee n ab le to perform its intended design function w ithout any adve rse effect. The spring was reset to within the design limit.
FORM OAR-1 OWNER ' S ACTIVITY REPORT
 
TABLES Report Number BFNU2R22 ---- -------- ---- -------- ------
PI ant Browns Ferry Unit No. 2 Commercia l service date 03/01/1975 Refueling outage no. 22 - ---
Current inspection interval 5th ----- Current inspection period 3rd - ------
TABLE 2 ABSTRACT OF REPAIR/REPLACEMENT ACTIVITIES REQUIRED FOR CONTINUED SERVICE Code Item Description Description of Work Date Repair/Replacement Class Completed Plan Number Rep lacement of BFN-2-FCV-068-0003 valve dra in line (3/4 ") leak.
Through wall leak was Flaw was removed with the d rain 1 line identified Design change was deta ia n d replaced with a 2 " line. 3-14-2023 123498959 led in Eng ineering Change Paper (ECP) number BFN-23 -018.
FORM OAR-1 OWNER'S ACTIVITY REPORT
 
TABLES Report Number BFNU2R22 --- ----------------------- ----
PI ant Browns Ferry Unit No. 2 Commercial service date 03/01/1975 Refueling outage no. 22 ----
Current inspection interval 5th Current inspection period 3rd ------------
REPORTING REQUIRED BY 10 CFR 50.55a(b)(2)(ix)(A)
ASME Section XI, Subsection IWE Steel Containment Vessel Inspection program
 
10 CFR 50.55a(b)(2)(ix)(A) requires reporting of the degradation assessment for inaccessible areas when conditions are identified in accessible areas during the performance of the ASME Section XI, Subsection IWE Steel Containment Vessel (SCV)
Inspection Program that could indicate the presence of or result in degradation to such inaccessible areas.
 
Browns Ferry Unit 2 is currently in the Third IWE Inspection Interval, Second Period. During BFN U2R22, there were no degradation assessments of inaccessible areas as a result of conditions identified in accessible areas during performance of the ASME Section XI, Subsection IWE SCV Inspection Program.
 
Examination Component Indication Acceptability/Corrective Action Inaccessible Additional Category and Identifier Description Area Samples Item Number (Location and Evaluation)
E-A, Item E 1.30 MSB-2-1 Mechanical During BFN 2R22, inspection of None None (Moisture Seal Damage the drywell Moisture Seal Barrier Barrier) identified unsatisfactory locations that cou ld potentially permit moisture intrusion into the inaccessible areas beneath the barrier. The MSB was excavated in these locations to make the steel containment vessel accessible and visually examined with no reportable conditions identified. Conditions were corrected by cleaning and replacing damaged areas of the MSB with no Repair/
Replacement Activity required.
The MSB was repaired with examination of the repaired sections having no reportable conditions. A post repair visual examination of the entire MSB was completed with no reportable conditions identified.}}

Latest revision as of 20:14, 13 November 2024

Amse,Section XI, Fifth 10 Year Inspection Interval, Inservice Inspection, System Pressure Test, Containment Inspection, and Repair and Replacement Programs, Owner’S Activity Report
ML23171A913
Person / Time
Site: Browns Ferry Tennessee Valley Authority icon.png
Issue date: 06/20/2023
From: Sivaraman M
Tennessee Valley Authority
To:
Office of Nuclear Reactor Regulation, Document Control Desk
References
Download: ML23171A913 (1)
v • d • e


Text

VALLEY TENNESSEE 1\\14 AUTHORITY

Post Office Box 2000, Decatur, Alabama 35609-2000

June 20, 2023 10 CFR 50.55a

ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, D.C. 20555-0001

Browns Ferry Nuclear Plant, Unit 2 Renewed Facility Operating License No. DPR-52 NRC Docket No. 50-260

Subject:

American Society of Mechanical Engineers,Section XI, Fifth 10 Year Inspection Interval, Inservice Inspection, System Pressure Test, Containment Inspection, and Repair and Replacement Programs, Owners Activity Report for Browns Ferry Nuclear Plant, Unit 2, Cycle 22 Operation

The Tennessee Valley Authority is submitting the Br owns Ferry Nuclear Plant (BFN), American Society of Mechanical Engineers (ASME),Section XI, Owners Activity Report for BFN, Unit 2, Cycle 22 Operation. The report is contained in the enclosure to this letter and is in accordance with the requirements of ASME Code Case N-532-5, Repair/Replacement Documentation Requirements and Inservice Summary Report Preparation and Submission,Section XI, Division 1.

The report is an overview of the inservice examination results that were performed on components within the ASME Section XI boundary, up to and including the BFN, Unit 2, Cycle 22 refueling outage, during the third inspection period of the Fifth 10 Year Inspection Interval. The applicable provisions of the ASME Code Case N-532-5 require t hat this report be submitted within 90 calendar days of the completion of each refueling outage. The BFN, Unit 2, Cycle 22 refueling outage ended on March 22, 2023. Accordingly, this submittal is due by June 20, 2023.

U.S. Nuclear Regulatory Commission Page 2 June 20, 2023

There are no new regulatory commitments contained in this letter. Should you have any questions concerning this submittal, please contact C. L. Vaughn, Site Licensing Manager, at (256) 729-2636.

Respectfully,

Manu Sivaraman Site Vice President

Enclosure:

American Society of Mechanical Engineers,Section XI, Fifth 10 Year Inspection Interval, Inservice Inspection, System Pressure Test, Containment Inspection, and Repair and Replacement Programs, Owners Activity Report for Browns Ferry Nuclear Plant, Unit 2, Cycle 22 Operation

cc (Enclosure): NRC Regional Administrator - Region II NRC Senior Resident Inspector - Browns Ferry Nuclear Plant NRC Project Manager - Browns Ferry Nuclear Plant

Enclosure

Tennessee Valley Authority

Browns Ferry Nuclear Plant Unit 2

American Society of Mechanical Engineers,Section XI, Fifth 10 Year Inspection Interval, Inservice Inspection, System Pressure Test, Containment Inspection, and Repair and Replacement Programs, Owners Activity Report for Browns Ferry Nuclear Plant, Unit 2, Cycle 22 Operation

See Enclosed

FORM OAR~1 OWNER'S ACTIVITY REPORT

Report Numbe r --"8'-'-F...,_N,..,U"-'2'-'-R_,_,2.,2~---- - ------- ----- ----- ------- ------- -

Plant Browns Ferry Nuc lear Pl<1nl. P 0. Box 2000 Decatur AL 35609

Unit No. - ---,-~2~-,- al service date March 1 1975 Refueling Outage no. --"'R~e~fl~'e"'li'-'n"'g_,O"-'u'-'-l'"ag"'e"-"-2,._2 __

(ir apph.: abl iC!-) Commerc i

Current Inspect ion Interval Fifth Ten Year inspection Interval

{ 151. 2M, 31 C1. m tier)

Current Inspection Period T~h~i~rd~P~e~ri=od~------- - -------::-c--::: -,-,-,---- ------ -------- p s,. 2n d, :!;, d)

2007 Edition, 2008 Addenda (ISi)

Edition and Addenda of Section XI applicable lo l11e inspection plans =2=0~13~E~d~it,~*o~n~(C=IS~IL) ---- ------ -------~

O-TPP-ENG-376, Revision 0004, 11/18/2022 O-Tl-364, Rev ision 0025, 02/06/2023 Dale and Rev ision of inspection plan 0-TPP-E NG-467 Revision 0001 01/12/2023

Edition and Addenda of Section XI applicable lo repairs and replacements, if different than the inspection plan ~N=IA~-

Code Cases used for inspection and evaluation : N-532-5 N-613-2 N-716-1 N-751 N-854. and N-864 (1I ap p hc.able, 1nc lu d 1r\\Q Crl:!>C~ mQd1f;ed b)' C a se N -S-32 anel la!Cr fC','1$kil'I~)

CERTIFICATE OF CONFORMANCE

I certify that (a) lhe statements made in this report are correc t (b) the ex aminations and tests meet the Inspection Plan as required by the ASME Code,Section XI ; and (c) the repair/replacement act ivities and evaluations supporting the completion of U2R22 conform to the requ iremen ts of Section XL '"' '"'""!l oota~ c ou mne r) s,,,.,f?~

CERTIFICATE OF INSERVICE INSPECTION

I, the und ersigned. holding a va lid commiss ion issued by the National Board of Boiler and Pressure Vessel Inspectors and employed by The Hartford Steam Bo iler lnspeclion and Insurance Company of Hartford Connect icut have inspected the items described in this Owne rs Activity Report and state that, to the best of my knowledge a nd belief, lhe Owner has performed all activities represented by this report in accordance with the requirements of Section XI.

By signing this certificate neither the Ins pec tor nor his emp loyer makes any warranty, expressed or implied, concerning the repair/ rep lacemen t act ivities and evalua tion described in this report. Furthermore, ne ither the Inspector nor his employer shall be liable in any manner for any personal 1n1ury o(. roperty damage or a loss of any kind arising from or connected with this Inspection P/~7, Comm issions f'Sf3. I ~q 71 L, N R...

FORM OAR-1 OWNER'S ACTIVITY REPORT

TABLES Report Number BFNU2R22 -------------------------------

PI ant Browns Ferry Unit No. 2 Commercia l service date 03/01/1975 Refueling outage no. 22 - ---

Cur rent inspection interval 5th Current inspection peri----- ----- - -od 3rd TABLE 1 ITEMS WITH FLAWS OR RELEVANT CONDITIONS THAT REQUIRE EVALUATIONS FOR CONTINUED SERVICE Exam ination Category and Item Number Item Description Evaluation Description F-A / F1.30C Residual Heat Removal Service Water NOi U2R22 -001 Variable Suppo rt, 2-4 7B450H0041 A variable spring support setting was found out of tolerance/ out of its load seeing range. It was determined that the as-found setting was w ithin the allowable working range, and that the va riable spring support wou ld have bee n ab le to perform its intended design function w ithout any adve rse effect. The spring was reset to within the design limit.

FORM OAR-1 OWNER ' S ACTIVITY REPORT

TABLES Report Number BFNU2R22 ---- -------- ---- -------- ------

PI ant Browns Ferry Unit No. 2 Commercia l service date 03/01/1975 Refueling outage no. 22 - ---

Current inspection interval 5th ----- Current inspection period 3rd - ------

TABLE 2 ABSTRACT OF REPAIR/REPLACEMENT ACTIVITIES REQUIRED FOR CONTINUED SERVICE Code Item Description Description of Work Date Repair/Replacement Class Completed Plan Number Rep lacement of BFN-2-FCV-068-0003 valve dra in line (3/4 ") leak.

Through wall leak was Flaw was removed with the d rain 1 line identified Design change was deta ia n d replaced with a 2 " line. 3-14-2023 123498959 led in Eng ineering Change Paper (ECP) number BFN-23 -018.

FORM OAR-1 OWNER'S ACTIVITY REPORT

TABLES Report Number BFNU2R22 --- ----------------------- ----

PI ant Browns Ferry Unit No. 2 Commercial service date 03/01/1975 Refueling outage no. 22 ----

Current inspection interval 5th Current inspection period 3rd ------------

REPORTING REQUIRED BY 10 CFR 50.55a(b)(2)(ix)(A)

ASME Section XI, Subsection IWE Steel Containment Vessel Inspection program

10 CFR 50.55a(b)(2)(ix)(A) requires reporting of the degradation assessment for inaccessible areas when conditions are identified in accessible areas during the performance of the ASME Section XI, Subsection IWE Steel Containment Vessel (SCV)

Inspection Program that could indicate the presence of or result in degradation to such inaccessible areas.

Browns Ferry Unit 2 is currently in the Third IWE Inspection Interval, Second Period. During BFN U2R22, there were no degradation assessments of inaccessible areas as a result of conditions identified in accessible areas during performance of the ASME Section XI, Subsection IWE SCV Inspection Program.

Examination Component Indication Acceptability/Corrective Action Inaccessible Additional Category and Identifier Description Area Samples Item Number (Location and Evaluation)

E-A, Item E 1.30 MSB-2-1 Mechanical During BFN 2R22, inspection of None None (Moisture Seal Damage the drywell Moisture Seal Barrier Barrier) identified unsatisfactory locations that cou ld potentially permit moisture intrusion into the inaccessible areas beneath the barrier. The MSB was excavated in these locations to make the steel containment vessel accessible and visually examined with no reportable conditions identified. Conditions were corrected by cleaning and replacing damaged areas of the MSB with no Repair/

Replacement Activity required.

The MSB was repaired with examination of the repaired sections having no reportable conditions. A post repair visual examination of the entire MSB was completed with no reportable conditions identified.

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